2. Bury, T. (2005). Analysis of thermal and flow processes within containments of water nuclear reactors during loss-of-coolant accidents. PhD thesis, Institute of Thermal Technology, Silesian University of Technology, Gliwice.
3. Fic, A., & Skorek, J. (1993). Mathematical model of transient thermal and flow processes in containment of a PWR nuclear reactor. Archiwum Energetyki, 1/2, 19–32.
4. Orszulik, M., Fic, A., Bury, T., & Składzień, J. (2013). A model of hydrogen passive autocatalytic recombiner and its validation via CFD simulations. Arch. Thermodyn., 34(4), 257–266.10.2478/aoter-2013-0042
5. Bury, T. (2002). Influence of the accident localization system construction on the course of the primary circuit rupture accident in VVER 440 units. Zeszyty Naukowe Politechniki Warszawskiej, seria Konferencje, 22(1), 169–176 (in Polish).
9. Debontride, B. (2006). Design of EPR. In Proceedings on International Conference on Nuclear Power Plants for Poland, 1–2 June 2006 (pp. 10.1-10.11). Warsaw, Poland.
10. AREVA. (2009). Applicability of AREVA NP containment response evaluation methodology to the U.S. EPR™ for large break LOCA analysis. AREVA NP Inc. (Technical Report No. 10299-NP, Revision 1).
11. Kostka, P., Techy, Z., & Sienicki, J. (2002). Hydrogen mixing analyses for a VVER containment. In Proceedings of 10th International Conference on Nuclear Engineering, 14–18 April 2002 (paper ICONE10-22206). Arlington, Virginia, USA.10.1115/ICONE10-22206